ASTM C1217-2000(2012) Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials 《核材料及放射性材料处理用设备设计的标准指南》.pdf

《ASTM C1217-2000(2012) Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials 《核材料及放射性材料处理用设备设计的标准指南》.pdf》由会员分享，可在线阅读，更多相关《ASTM C1217-2000(2012) Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials 《核材料及放射性材料处理用设备设计的标准指南》.pdf（19页珍藏版）》请在麦多课文档分享上搜索。

1、Designation: C1217 00 (Reapproved 2012)Standard Guide forDesign of Equipment for Processing Nuclear andRadioactive Materials1This standard is issued under the fixed designation C1217; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision,

2、 the year of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.1. Scope1.1 Intent:1.1.1 This guide covers equipment used in shielded cell orcanyon facilities for the processing of

3、nuclear and radioactivematerials. It is the intent of this guide to set down theconditions and practices that have been found necessary toensure against or to minimize the failures and outages ofequipment used under the subject circumstances.1.1.2 It is intended that this guide record the principles

4、 andcaveats that experience has shown to be essential to the design,fabrication, and installation of equipment capable of meetingthe stringent demands of operating, dependably and safely, ina nuclear processing environment that operators can neither seenor reach directly.1.1.3 This guide sets forth

5、generalized criteria and guide-lines for the design, fabrication, and installation of equipmentused in this service. This service includes the processing ofradioactive wastes. Equipment is placed behind radiationshield walls and cannot be directly accessed by the operators orby maintenance personnel

6、 because of the radiation exposurehazards. In the type of shielded cell or canyon facility ofinterest to users of this guide, either the background radiationlevel remains high at all times or it is impractical to remove theprocess sources of radiation to facilitate in situ repairs or carryout mainte

7、nance procedures on equipment. The equipment isoperated remotely, either with or without visual access to theequipment.1.2 Applicability:1.2.1 This guide is intended to be applicable to equipmentused under one or more of the following conditions:1.2.1.1 The materials handled or processed constitute

8、asignificant radiation hazard to man or to the environment.1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), butequipment intended for use over a shorter life cycle is notexcluded.1.2.1.3 The material handled or processed must be retained

9、,contained, and confined within known bounds for reasons ofaccountability or to minimize the spread of radioactive con-tamination.1.2.1.4 The materials handled or processed must be kept andmaintained within one or more of the following conditions:(1) In a specific geometric array or configuration, a

10、nd(2) Within a range of conditions that have been determinedto be a critically safe set of conditions for that piece ofequipment, that is, 1) in a given and specified operationalposition where adjacent nuclear criticality interaction condi-tions are known and unchanging, 2) for a given and specified

11、set or range of operating conditions, and 3) for a given andspecified process.1.2.1.5 The equipment can neither be accessed directly forpurposes of operation or maintenance, nor can the equipmentbe viewed directly, for example, without intervening shieldedviewing windows, periscopes, or a television

12、 monitoring sys-tem.1.2.2 This guide is intended to be applicable to the design ofequipment for the processing of materials containing uraniumand transuranium elements in any physical form under thefollowing conditions:1.2.2.1 Such materials constitute an unacceptable radiationhazard to the operator

13、s and maintenance personnel,1.2.2.2 The need exists for the confinement of the in-processmaterial, of dusts and particulates, or of vapors and gasesarising or resulting from the handling and processing of suchmaterials, and1.2.2.3 Any of the conditions cited in 1.2.1 apply.1.2.3 This guide is intend

14、ed to apply to the design, fabrica-tion, and installation of ancillary and support services equip-ment under the following conditions:1.2.3.1 Such equipment is installed in shielded cell orcanyon environments, or1This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is

15、the direct responsibility of Subcommittee C26.09 on NuclearProcessing.Current edition approved June 1, 2012 Published June 2012 . Originallyapproved in 2000. Last previous edition approved in 2006 as C121700(2006). DOI:10.1520/C1217-00R12.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box

16、C700, West Conshohocken, PA 19428-2959, United States.1.2.3.2 Such equipment is an integral part of an in-cellprocessing equipment configuration, or an auxiliary componentor system thereof, even though an equipment item or systemmay not directly hold or contain nuclear or radioactive mate-rials unde

17、r normal processing conditions.NOTE 1Upsets, accidents, or certain emergency conditions may bespecified (and thus required) design considerations, but not necessarilyacceptable or normal operating circumstances under this definition.1.2.4 This guide is intended to apply to the design andfabrication

18、of any and all types of equipment for radioactivewastes processing when any of the conditions cited in 1.2.1apply. This would include equipment for waste concentration;for incorporation of wastes in selected host materials ormatrices; and for the fixation, encapsulation, or canning of suchwastes. It

19、 is intended to apply to all such wastes, regardless ofthe product waste composition or form. The product radioac-tive waste may have a glass, ceramic, metallic, concrete,bituminous, or other type of host material or matrices (com-position), and may be in pelletized, solid, or granular form.1.3 User

20、 Caveats:1.3.1 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.NOTE

21、 2Warning: This standard pertains to equipment used in and forthe handling and processing of nuclear and radioactive materials. Theseoperations are known to be hazardous for a variety of reasons, one beingchemical toxicity.1.3.2 This standard is not a substitute for applied engineer-ing skills. Its

22、purpose is to provide guidance.1.3.2.1 The guidance set forth in this standard relating todesign of equipment is intended only to alert designers andengineers to those features, conditions, and procedures thathave been found necessary or highly desirable to the acquisi-tion of reliable equipment for

23、 the subject service conditions.1.3.2.2 The guidance set forth results from discoveries ofconditions, practices, features, or lack of features that werefound to be sources of operational or maintenance trouble, orcauses of failure.1.3.3 It is often necessary to maintain the materials beingprocessed

24、within specific chemical composition or concentra-tion ranges, or both. When such constraints apply, it may alsobe necessary to create and maintain a specific geometric arrayto minimize the chances of a nuclear criticality incident.Designers and engineers are referred to other standards foradditiona

25、l guidance when such requirements apply.1.3.4 Equipment usage intent, service conditions, size andconfiguration, plus the configuration and features of the oper-ating and maintenance environments have an influence onequipment design. Therefore, not all of the criteria, conditions,caveats, or feature

26、s would be applicable to every equipmentitem.1.3.5 It is intended that equipment designed, fabricated,procured, or obtained by transfer or adaptation and re-use ofexisting equipment, and installed in accord with the standardmeet or exceed statutory, regulatory, and safety requirementsfor that equipm

27、ent under the applicable operating and serviceconditions.1.3.6 This standard does not supersede federal or stateregulations, or both, and codes applicable to equipment underany conditions.2. Referenced Documents2.1 Industry and National Consensus StandardsNationally recognized industry and consensus

28、 standards appli-cable in whole or in part to the design, fabrication, andinstallation of equipment are referenced throughout this guideand include the following:2.2 ASTM Standards:2C859 Terminology Relating to Nuclear MaterialsD5144 Guide for Use of Protective Coating Standards inNuclear Power Plan

29、ts2.3 ANSI Standards:3ANSI/ANS 8.1 Nuclear Criticality Safety in Operationswith Fissile Materials Outside ReactorsANS Glossary of Terms in Nuclear Science and Technol-ogy (ANS Glossary)ANSI A14.3 Ladders, Fixed Safety Requirements2.4 ASME Standard:4Boiler and Pressure Vessel Code, Section VIIIASME N

30、QA1 QualityAssurance Requirements for NuclearFacility ApplicationsASME NOG-1, Rules for Construction of Overhead GantryCranes (Top-Running Bridge, Multiple Girder)2.5 Federal Regulations:510CFR50, Appendix B, Quality Assurance29CFR1910, Occupational Safety and Health Standards2.6 National Electrical

31、 Manufacturers Association (NEMA)Standards:6NEMA 250 Enclosures for Electrical Equipment 1000 VoltsMaximum (Type 4)2.7 National Fire Protection Association (NFPA) Stan-dards:7NFPA 70, National Electric Code3. Terminology3.1 Definitions:3.1.1 The terminology employed in this guide conformswith indust

32、ry practice insofar as practicable.3.1.2 For definitions of terms used in this guide, refer toTerminology C859 and ANS Glossary.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume informatio

33、n, refer to the standards Document Summary page onthe ASTM website.3Available from American National Standards Institute, 11 W. 42ndSt., 13thFl.,New York, NY 10036.4Available from American Society of Mechanical Engineers, 3 Park Ave., NewYork, NY 10016.5Available from U.S. Government Printing Office

34、, Superintendent of Docu-ments, Mail Stop SSOP, Washington, DC 20402-9328.6Available from Global Engineering Co., 15 Inverness Way, Englewood, CO80112.7Available from National Fire Protection Agency (NFPA), One BatterymarchPark, Quincy, MA 02269.C1217 00 (2012)23.2 Descriptions of Terms Specific to

35、This StandardTheterms defined below are of a restricted nature, specificallyapplicable to this guide.3.2.1 accidentan unplanned event that could result inunacceptable levels of any of the following: (1) equipmentdamage, (2) injury to personnel, (3) downtime or outage, (4)release of hazardous materia

36、ls (radioactive or non-radioactive),(5) radiation exposure to personnel, or (6) criticality.3.2.2 accountabilitythe keeping of detailed records on,and the responsibilityon the part of operations personnel andplant managementof being accountable for the amounts ofspecial nuclear materials entering an

37、d leaving a plant, a vessel,or a defined processing step.3.2.3 datum connection pointsthose locations on equip-ment where separate auxiliary equipment items such as pumps,agitators, columns, condensers, and other separately removableequipment pieces are mounted, or where process, service,instrumenta

38、tion, or electrical jumper connections are made.3.2.3.1 DiscussionThese datum connection points are po-sitioned by dimensioning from (theoretically) perfectly placedbase X, Y and Z datum planes; for example, such points orlocations are dimensionally located by three-plane coordinatedimensions. Datum

39、 connection points are the loci of position-ing elements such as dowels, trunnions, trunnion guides, andsuch other devices or elements that serve to align, position, orlocate equipment in a precise position or array, or which serveas a point for the connection or placement of other compo-nents.3.2.4

40、 engineering responsibilityan obligation to performengineering design activities assigned to a specified organiza-tion.3.2.5 geometrically favorableequipment having set di-mensions, and a shape or a layout configuration, that providesassurance that a criticality incident cannot occur in the equip-me

41、nt or system under a given set of circumstances or condi-tions.3.2.5.1 DiscussionThe given set of conditions or circum-stances requires that the isotopic composition, form, concen-tration, and density of fissile materials in the equipment orsystem will not violate those assumed and used for theprepa

42、ration of the criticality analysis, and that those variableswill remain within conservatively chosen limits, and thatnuclear criticality interaction conditions will be within somepermitted, pre-set range.3.2.6 jumpersthe pipe line, electrical service, or instru-mentation service connector assemblies

43、 that span the gapbetween nozzles or connection points on the canyon orcell-mounted equipment and (1) nozzles or connection pointson adjacent or nearby vessels, or (2) service nozzles orconnector points on the interior sides of the cell or shield walls.3.2.7 owner-operatorthe firm having either lega

44、l owner-ship responsibilities and rights for the nuclear and radioactivematerials handling/processing facility where subject equipmentis to be installed or used, or both, or the firm that has acceptedall management, engineering, operation, and maintenance re-sponsibilities and rights (or specified p

45、ortions thereof) by wayof contractual arrangement(s) with the legal owner of thefacilities.4. Significance and Use4.1 Equipment operability and long-term integrity are con-cerns that originate during the design and fabrication se-quences. Such concerns can only be addressed or are mostefficiently ad

46、dressed during one or the other of these stages.Equipment operability and integrity can be compromisedduring handling and installation sequences. For this reason, thesubject equipment should be handled and installed underclosely controlled and supervised conditions.4.2 This guide is intended as a su

47、pplement to other stan-dards, and to federal and state regulations, codes, and criteriaapplicable to the design of equipment intended for this use.4.3 This guide is intended to be generic and to apply to awide range of equipment types and configurations.4.4 The term equipment is used herein in a gen

48、eric sense.See 3.2.5 for the definition.4.5 This service imposes stringent requirements on thequality and the integrity of the equipment, as follows:4.5.1 Leak tightness is required. This implies containmentof liquids at all times, and retention of vapors and gases bymeans of vessel design, or throu

49、gh means of engineeredprovisions or operational procedures, or both, that ensure theretention, collection, and treatment of vapors and off-gaseswhen the vessel cannot be fabricated or operated with anair-tight vessel configuration. Radioactive materials must becontained.4.5.2 Equipment must be capable of withstanding rigorouschemical cleaning and decontamination procedures.4.5.3 Equipment must be designed and fabricated to remaindimensionally stable throughout its life cycle.4.5.4 Close fabrication tolerances are required to set nozzlesand other datum points in known p